ML20213E609

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Response to NRC Second Set of Inerrogatories Re Proposed Reracking of Spent Fuel Pools.Not Possible to Either Identify or Supply All Ref Documentation Supporting Contentions.W/Proof of Svc.Related Correspondence
ML20213E609
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 11/06/1986
From: Grueneich D
GRUENEICH, D.M. (FORMERLY GRUENEICH & LOWRY), Sierra Club
To:
NRC COMMISSION (OCM)
References
CON-#486-1441 OLA, NUDOCS 8611130228
Download: ML20213E609 (22)
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R[lfTED CORRESPO.NDMfg UNITED STATES OF AMERICA 00LKETED NUCLEAR REGULATORY COMMISSION J

'SNPC BEFORE THE ATOMIC SAFETY AND LICENSING B g DNOV 10 P4 :46 l

i

) DFFICE Di ~ .

In the Matter of: ) Docket Nos. 50-2 fgCr Md a t:50 J323 t-OLN

)

PACIFIC GAS & ELECTRIC COMPANY ) (Reracking of Spent Fuel Pools)

)

(Diablo Canyon Nuclear Power )

Plant, Units 1 and 2) ) I

)  !'

l-SIERRA CLUB'S RESPONSES TO UNITED STATES NUCLEAR REGULATORY COMMISSION STAFF'S SECOND SET OF INTERROGATORIES 2-la. The Sierra Club's contentions regarding the proposed reracking and alternatives are based on an understanding of the existing industry practice and, in general, the currently available technology for the storage of spent fuel. This understanding was derived from a review of existing literature on reracking, generic research documentation generated by the federal government, and other sources discussing spent fuel storage and alternatives. It is not possible to either identify or supply all of the reference documentation supporting the contentions. However, specific documents that are available and which are directly related to the Sierra Club's contentins include the Reports and answers prepared by Dr. Ferguson. In  ;

addition, the Sierra Club relies upon the documents filed and made available by both PG&E and the NRC in this proceeding and in the NRC's review of the reracking. Sierra Club also relies upon the opinion of the Ninth Circuit Court of Appeals on the Diablo 1

8611130228 PDR 861106 G ADOCK 05000275 PDR

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l' Canyon reracking, including its " strong suggestion" that the NRC update'and expand its NEPA documents which, by law, must address alternatives.

2-1.b. The Sierra Club is not aware of addresses, educa-tion, or professional qualifications beyond the information presented in the publicly available documents in this proceeding.

A copy of Dr. Ferguson's qualifications is attached.

2-1.c. The Sierra Club has not yet determined which witnesses it will call beyond Dr. Ferguson. Pacific Gas and Electric Company has the burden of showing that its license application should be granted. The NRC is responsible, under NEPA, for its review of alternatives. These two parties have the burden of demonstrating, through evidence and witnesses, that the license should be granted and that the review has been adequate.

Additional witnesses beyond Dr. Ferguson that the Sierra Club calls will depend upon the witnesses and testimony that the NRC staff and PGGE seek to introduce.

2-2. No proposed testimony or summaries beyond the docu- '

ments filed are available yet. For Dr. Ferguson, documents he [

relies upon include answers to the first and second set of interrogatories.

3 e

2-3. See answers to Interrogatories 2-1 to 2-3 above.

2-4. Unknown. Since the burden of proof is on the NRC and PG&E, the exhibits that the Sierra Club will use will depend upon i

what exhibits and testimony the NRC and PG&E rely upon at the L hearing. It is of course impossible to state what exhibits would 2  ;

i

_ _ _ . . _ _ _ _ _ , .~. _ _ . ,--_ _ _ _ , - _ . , _ _ _ _ --

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i be used for cross-examination until the NRC, PG&E and other l parties file their testimony, i

2-5. The large quantities of heat and radiation referred to would occur due to an accident causing damage to the racks resulting in the fuel exceeding criticality. See Response of the Sierra Club . to the First Set of Interrogatories, pp. 24-25

(" Report").

2-6. Information is provided on pp. 11-15 of the Report and .

in these answers. In addition, the following is a further I discussion regarding the appropriate treatment of frictional forces during collisions. Initial analytical models ignored all dissipative forces so that the collision was elastic for simpli-city. In these models, impact forces were found to be large compared with maximum frictional forces, indicating that the approximation was appropriate.

In the time-history collision model used by Dr. Ferguson in the Report, friction was included with the coefficient as an adjustable parameter. (See, for example, line 2760 of the computer program COLL 4050.) In that model, the direction of the frictional force was taken to oppose the relative motion of the rack, in the usual way. Thus, during the " rebound" of the rack, the frictional force opposes the wall force.

It should be pointed out that the rack models used by both PG&E and Dr. Ferguson are highly simplistic in the way they model the collision of the base plate. In both, the elasticity of the upper part of the rack at the girdle bar is taken to be the same 3

l

as the base plate. In fact, the response of the top and bottom is expected to be quite different. The actual behavior of the j rack-floor interface during a collision is not discussed by any author. Given this uncertainty, it would be prudent to choose the most conservative model. If, by ignoring friction during collisions, larger rack forces are predicted, it is advisable to use them.

2-7. It is unclear what is meant by " logic change". ,

Insofar as Sierra Club understands the term, no such changes ,

occur. The values of the parameters used in COLL 4050 are as ,

follows (all units are pounds, feet and seconds):

LINE 200 KW = 4.8EO7

  • rack elasticity representing the parallel combination of four corner springs for rack-wall interactions.

LINE 210 KI = 1.68E06

  • cell wall elasticity for series and parallel combinations corresponding to 10xil rack.

LINE 211 MU = .2 to .8

  • coefficient of friction.

LINE 212 GAP = 0 to .5

  • spacing between fuel and cell wall at time of impact.

LINE 213 EFF = 1* " effective mass" multiplier (Ref. 6).

LINE 214 VRF = .5

  • rack speed at time of impact.

LINE 230 DELT = .0002

  • integration step size.

i LINE 280 MF = 55 X 1616/ GEE

  • moving fuel mass ,

MR = MF + 28000/ GEE

  • mass fixed to rack 2-8. The two-dimens.ional model used considers a maximum of three horizontal forces on the rack: friction from the floor contacts, called FRICTION in the program; an impact force from the wall, WALLIMP, if the rack is in contact with the wall, and an impact force from the fuel, FUELIMP, if the fuel is in contact l

4 h

with the rack. (See figure 2.) The equations of motion appear in the program at lines 2790 and 2800. Moments and rotations are not included.

The program COLL 4050 does not output values of FUELIMP as presently written.

The addition of a line at 3136 such as 3136 PRINT FUELIMP would output values every millisecond of the time history for whatever input parameters were chosen.

The user is fran to vary these paramctors at will. By modifying COLL 4050 to output FUELIMP or other parameters, the user can examine the relationships of forces, displacements, velocities, etc.,

in whatever combinations are desired for any choice of initial conditions. Indeed, it was to obtain this i

flexibility that the program was written.

2-9. The " double impact" depicted on Figures 2 and 3 is e described on pages 12-13 of the Report. With the enclosed computer program, the user can investigate any parametric relationships for all times by running the program with the desired input parameters.

2-10. The analysis of the response of a free rack to the PHE is modeled in the program D3 SLIDE. The freebody diagram used for D3 SLIDE is similar to that used for COLL 4050 (Fig. 1) with the absence of WALLIMP and the inclusion of a second horizontal dimension. In the D3 SLIDE model, motion in both horizontal i

directions is included, as well as the vertical. Rattling of the fuel and the resulting impacts with the rack are also accounted for, although the present version does not include fluid coupling I

5 l

1

r forces between fuel and rack. Rotations and moments are ignored, so that the result is a model with five degrees of freedom.

Another feature of this model is that pool accelerations are linearly interpolated between the step values given by the PHE.

This interpolation procedure is found to have little qualitative effect on the results, however.

A listing of the program and a printout of some parameters ,

tor the first six seconds of the PHE are provided as attachments  :

to this response. As can be seen from the printout, relative rack displacements are several inches (see, for example, times 4.8 through 5.2) and relative rack speeds exceed two feet per second (see, for example, time 4.88).

2-11. The collision is assumed to occur at 4.050 seconds into the PHE, with the impact speed as an adjustable parameter.

The speed of the rack used for Figure 1 is 1.0 ft/sec. The seismic inputs used for COLL 4050 are the east-west values from the PHE. The portion of the PHE time history used for COLL 4050 is from 4.050 seconds to 4.20 seconds.

2-12.a. The convergence of COLL 4050 was checked by varying I the parameter DELT in line 230 of the program and checking the variation of the maximum value of WALLIMP. Given the relatively short time period of the time-history (150 ms) the output was not expected to be as sensitive as if the entire 24 second time history were analyzed. The check was performed for the non-linear seismic response.

2-12.b. To benchmark the program, the output must be 1

6 i

i

compared with known results. These were obtainable from the simple elastic analytical expression.

2-13. Given that Dr. Ferguson is responsible for the contents of the Report, the Sierra Club objects to disclosure of names of persons reviewing the Report absent a demonstration that such information is necessary or relevant to the NRC staff's review. Moreover, Dr. Ferguson has discussed his analysis and Report with many people and it is impossible to identify all of those who may have contributed to his analysis.

Dated: November 6, 1986 GRUENEICH & LOWRY By / ,/I, . .

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. / / f 7~/ W c, --- D8N & L iREM /* "D3 SLIDE" COMPUTES MOTION OF RACK CONSIDERING 5 DOF */ '

I REM /* ROTATIONS NOT CONSIDERED */

REM /* STRUCTURAL DAMPING NOT CONSIDERED */

REM /* FLUID COUPLING NOT CONSIDERED */

REM /* FRICTION FULLY ACCOUNTED FOR */

REM /* INTERNAL MOTION OF FUEL ACCOUNTED FOR */

O MU = .2: GEE = 32.15 O MR = (28000 + 55

  • 1616) / GEE: MF = (55
  • 1616) / GEE: MTOT = MR + MF O DELT = .001: NUMDIVS = .01 / DELT lO IO KIX = 154000!
  • 12: KIY = 127000!
  • 12

.302 / 12: GAPY = .302 / 12 f5GAPX=

O DIM EWHSTACNUMDIVS): DIM NSHSTACNUMDIVS): DIM VZHSTACNUMDIVS) kO OPEN "I", #1, "B:EWHSTA"

  1. 2, "B:NSHSTA" f0OPEN"I".

O OPEN "I", #3. "B:VZHSTA" i

  • I f0

~O FOR THE = .01 TO 24 STEP .01  :

f0GOSUB900 l

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s0 FOR J = 1 TO NUMDIVS IO AWX = GEE

  • EWHSTACJ): AWY = GEE
  • NSHSTACJ): AWZ = GEE
  • VZHSTACJ)

I O' f5GOSUB1400: REM /* NORMAL FORCE */

c0 GOSUB 1200: REM /* FRICTION */

I O GOSUB 1000: REM /* FUEL ACC */

~O GOSUB 1300: REM /* RACK ACC */

O VWX = VWX + AWX

  • DELT: VRX = VRX + ARX
  • DELT: VFX = VFX + AFX
  • DELT (O XWX = XWX + VWX
  • DELT: XRX = XRX + VRX ** DELT: XFX = XFX + VFX DELT O VWY = VWY + AWY
  • DELT: VRY = VRY + ARY DELT: VFY = VFY + AFY
  • DELT O XWY = XWY + VWY
  • DELT: XRY = XRY + VRY
  • DELT: XFY = XFY + VFY
  • DELT 3 VWZ = VWZ + AWZ
  • DELT: VRZ = VRZ + ARZ
  • DELT 0 XWZ = XWZ + VWZ
  • DELT: XRZ = XRZ + VRZ
  • DELT O VRWX = VRX - VWX: VRWY = VRY - VWY XRFY = XRY - XFY f0XRFX=XRX-XFX:

O XRWX = XRX - XWX: XRWY = XRY - XWY 00 NEXT J O PRINT USING "###.###";TME TABC9);XWX; TABC18); VWX; TABC27) XRWX; TABC36);

"WX ; TABC45); XRWY; TABC54); VRWY 5 LPRINT USING "###.###";TME TABC9);XWX; TABC18); VWX; TABC27) XRWX; TABC36); ,

RWX; TABC45); XRWY; TABC54); VRWY I

7 IF TME*100 MOD 60 = 0 THEN LPRINT:LPRINT:LPRINT:LPRINT:LPRINT:LPRINT O NEXT TME T

O CLOSE: END 0*

O REM /* LOADS ARRAYS */

'O EWHSTACO) = EWHSTACNUMDIVS): NSHSTACO) - NSHSTACNUMDIVS): VZHSTACO) = VSHSTA UMDIVS)

O INPUT #1, EWHSTACNUMDIVS): INPUT #2, NSHSTACNUMDIVS): INPUT #3, VZHSTACNUMDI '

)

60 FOR I = 1 TO NUMDIVS -1 ~

0 EWHSTACI) = CI / NUMDIVS)

  • CEWHSTACNUMDIVS) - EWHSTACO)) + EWHSTACO) l 4 *

-O NSHSTACI) = CI / NUMDIVS) CNSHSTACNUMDIVS) - NSHSTACO)) + NSHSTACO) '

f0VZHSTACI)

CI / NUMDIVS) CVZHSTACNUMDIVS) -

VZHSTACO)) + VZHSTACO) p0 NEXT I

[O RETURN

.0

  • COO REM /* FRICTION CALCULATIONS -- RETURNS WITH FRX, FRY */

05 MUNORM - MU

  • FRZ

p.

10 VRWXY - SOR( VRWX^2 + VRWY^2) 20 IF VRWXY > .0001 THEN GOSUB 1050 ELSE GOSUB 1110 e40 RETURN 50 REM /* RACK SLIPPING */

O FRX = - MUNORM

  • VRWX / VRWXY: FRY = - MUNORM
  • VRWY / VRWXY O RETURN g80 e:90 00 REM /* RACK NOT YET SLIPPING */

'10 FRE0X = MR

  • AWX + FFX: FRE0Y = MR
  • AWY + FFY

$20 FRE0XY = SORCFREQX^2 + FRE0Y^2) 30 IF FRE0XY > MUNORM THEN RATIO - MUNORM / FRE0XY ELSE RATIO = 1 640 FRX = FRE0X

  • RATIO: FRY = FREQY
  • RATIO SO RETURN "200 REM /* FUEL ACCELERATION CALCULATIONS */

10 REM /* CALL BEFORE FRICTION CALCS */

'20 IF ABSCXRFX) - GAPX < 0 THEN FFX = 0 ELSE FFX = KIX

  • CABSCXRFX) - GAPX)
  • NCXRFX) 30 IF ABSCX2FY) - GAPY < 0 THEN FFY = 0 ELSE FFY = KIY
  • CAESCXRFY) - GAPY) *S CXRFY) 40 AFX = FFX / MF: AFY = FFY / MF 50 RETURN 00 REM /* RACK ACCELERATION CALCULATIONS */

L10 REM /* CALL FUEL ACC AND FRICTION CALCS FIRST */

s2O ARX = CFRX - FFX) / MR: ARY = (FRY - FFY) / MR: ARZ = FRZ / MTOT - GEE 30 RETURN 00 REM /* NORMAL FORCE CALCS */

10 FRZ = MTOT

  • CAWZ 4 GEE) 20 RETURN L

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+ 0.660 -0.041 0.304 -0.003 -0.005 -0.002 -0.007 0.670 -0.038 0.311 -0.003 -0.000 -0.002 -0.004 0.600 -0.035 0.317 -0.003 -0.000 -0.002 -0.001 0.690 -0.032 0.322 -0.003 0.002 -0.002 0.001 0.700 -0.029 0.325 -0.003 0.000 -0.002 0.003 0.710 -0.025 0.025 -0.003 -0.003 -0.002 0.005 0.720 -0.022 0.321 -0.003 -0.007 -0.002 0.006 0.730 -0.019 0.313 -0.000 0.003 -0.002 -0.000 0.740 -0.016 0.303 -0.003 0.003 -0.002 -0.001 0.750 -0.013 0.290 -0.003 0.000 -0.002 0.004 0.760 -0.010 0.277 -0.003 0.011 -0.002 0.001 0.770 -0.007 0.264 -0.003 0.005 -0.002 -0.003 0.780 -0.005 0.252 -0.003 0.000 -0.002 0.001 0.790 -0.002 0.240 -0.003 -0.005 -0.002 0.006 0.800 -0.000 0.230 -0.003 0.006 -0.002 -0.006 0.810 0.002 0.220 -0.003 0.009 -0.002 -0.003 0.820 0.004 0.210 -0.003 0.006 -0.002 -0.000 0.830 0.006 0.202 -0.003 0.017 -0.002 -0.001 0.840 0.000 0.193 -0.003 -0.004 -0.002 -0.000 0.850 0.010 0.183 -0.003 0.009 -0.002 -0.000 0.860 0.012 0.170 -0.003 0.007 -0.002 0.000 0.870 0.014 0.155 -0.003 0.009 -0.002 0.001 0.880 0.015 0.141 -0.003 0.006 -0.002 0.001 0.890 0.016 0.130 -0.002 0.017 -0.002 0.002 0.900 0.018 0.121 -0.002 0.014 -0.002 0.001 0.910 0.019 0.112 -0.002 -0.004 -0.002 -0.000 0.920 0.020 0.102 -0.002 0.008 -0.002 0.001 0.930 0.021 0.091 -0.002 0.004 -0.002 0.001 0.940 0.022 0.078. -0.002 -0.005 -0.002 -0.001 0.950 0.022 0.063 -0.002 0.010 -0.002 0.007 0.960 0.023 0.045 -0.002 0.010 -0.002 0.005 0.970 0.023 0.022 -0.002 0.011 -0.002 0.006 0.980 0.023 -0.002 -0.002 -0.005 -0.002 -0.002 0.990 0.023 -0.027 -0.002 -0.003 -0.002 -0.000 1.000 0.023 -0.050 -0.002 -0.001 -0.002 -0.000 a 1.010 0.022 -0.078 -0.002 0.004 -0.002 0.001

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, 4.540 -0.799 -1.333 0.198 0.529 -0.000 1.241 4.550 -0.813 -1.300 0.203 0.487 0.012 1.205 4.560 -0.825 -1.228 0.207 0.398 0.024 1.188 4.570 -0.837 -1.145 0.211 0.292 0.036 1.166 4.580 -0.848 -1.071 0.213 0.195 0.047 1.124 4.590 -0.859 -1.060 0.215 0.164 0.058 1.064 4.600 -0.869 -1.097 0.216 0.179 0.069 0.990 4.610 -0.881 -1.099 0.218 0.160 0.078 0.897

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. 5.970 -1.071 0.868 -0.081 -0.634 -0.234 1.580 5.980 -1.063 O.771 -0.087 -0.502 -0.218 1.665 5.990 -1.056 0.713 -0.091 -0.417 -0.201 1.709 6.000 --1.049 0.699 -0.095 -0.379 -0.183 1.720

i QUALIFICATIONS OF DR. RICHARD B. FERGUSON Dr. Ferguson is a professional physicist, Vice-Chairman and Conservation Chairman of the Sierra Club, Santa Lucia Chapter, and a Pacific Gas & Electric Company ratepayer. He received a Bachelor of Arts degree, cum laude, from Amherst College, Massachusetts in 1960 and a Ph.D. in physics from Washington University, St. Louis, Missouri in 1967. Dr. Ferguson taught on the physics faculty of the University of California at Los Angeles from 1967 to 1970 and of California Polytechnic Univer-sity at San Luis Obispo from 1974 to 1984. He resides in San Luis Obispo County at Rocky Canyon Star Route, Creston, Califor-nia 93432.

On behalf of the Sierra Club, on February 10, 1986, he requested a hearing and filed a petition for leave to intervene in the NRC proceeding related to PG&E's request for a license amendment to permit reracking of the spent fuel storage facili-ties for the Diablo Canyon nuclear power plant. The Sierra Club filed its petition because of its concerns about the environment and public health and safety.

PROOF OF SERVICE gg I, Deborah M. Hunt, declare that on November 6, 198N', I deposited copies of the attached Sierra Club's Responses to United States Nuclear Regulatory Commission Staff's Secongg Qg$ jgfp4 :46 Interrogatories in the United States mail with postage thereon fully prepaid and addressed to the parties listed below:

6FFIL 4 -

Dr. Jerry Harbour Mr. Leland M. Gustaf soROCKEijNi i*V10 Administrative Judge Federal Relations Manage $

Atomic Safety & Licensing Board Pacific Gas & Electric Co.

U.S. Nuclear Regulatory Comm. 1726 "M" Street, NW, Suite 1100 Washington, D.C. 20555 Washington, D.C. 20036-4502 Glenn O. Bright Philip A. Crane, Jr., Esq.

Administrative Judge Pacific Gas & Electric Co.

Atomic Safety & Licensing Board P.O. Box 7442 U.S. Buclear Regulatory Comm. San Francisco, CA 94120 Washington, D.C. 20555 Mr. Gordon A. Silver Henry J. McGurren, Esq. Ms. Sandra A. Silver Lawrence J. Chandler, Esq. 1760 Alisal Street Office of the Exec. Legal Dir. San Luis Obispo, CA 93401 U.S. Nuclear Regulatory Comm.

Washington, D.C. 20555 Ms. Laurie McDermott, Coordinator Atomic Safety & Licensing C.O.D.E.S.

Board Panel 731 Pacific Street, Suite 42 U.S. Nuclear Regulatory Comm. San Luis Obispo, CA 93401 Washington, D.C. 20555 Mrs. Jacquelyn Wheeler B. Paul Cotter, Jr., Chairman 2455 Leona Street Administrative Judge San Luis Obispo, CA 93400 Atomic Safety & Licensing Board U.S. Nuclear Regulatory Comm. Dr. R.B. Ferguson Washington, D.C. 20555 Sierra Club / Santa Lucia Chapter Rocky Canyon Star Route Atomic Safety & Licensing Creston, CA 93432 Appeal Panel U.S. Nuclear Regulatory Comm. Ms. Nancy Culver Washington, D.C. 20555 192 Luneta Street San Luis Obispo, CA 93401 Bruce Norton, Esq.

NORTON, BURKE, BERRY & FRENCH P.O. Box 10569 Phoenix, AZ 85064 I am, and was at the time of the service of the attached paper, over the age of 18 and not a party to the proceeding.

I declare under penalty of perjury that the foregoing is true and correct.

i /

~

_( .

Deborah M. Hunt

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